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http://dx.doi.org/10.5516/NET.2010.42.2.193

PROPERTIES OF ZR ALLOY CLADDING AFTER SIMULATED LOCA OXIDATION AND WATER QUENCHING  

Kim, Hyun-Gil (Nuclear Convergence Technology Division, Korea Atomic Energy Research Institute)
Kim, Il-Hyun (Nuclear Convergence Technology Division, Korea Atomic Energy Research Institute)
Jung, Yang-Il (Nuclear Convergence Technology Division, Korea Atomic Energy Research Institute)
Park, Jeong-Yong (Nuclear Convergence Technology Division, Korea Atomic Energy Research Institute)
Jeong, Yong-Hwan (Nuclear Convergence Technology Division, Korea Atomic Energy Research Institute)
Publication Information
Nuclear Engineering and Technology / v.42, no.2, 2010 , pp. 193-202 More about this Journal
Abstract
In order to study the cladding properties of zirconium after a loss-of-coolant accident (LOCA)-simulation oxidation and water quenching test, commercial Zircaloy-4 and two kinds of HANA claddings were oxidized at temperatures ranging from $900^{\circ}C$ to $1250^{\circ}C$ and exposed for 300 s, and then cooled to $700^{\circ}C$ before quenching. Microstructural observations were made to evaluate the matrix characteristics with the chemical compositions after the LOCA-simulation test. Ring compression testing was then performed to compare the ductile behaviour of the HANA and Zircaloy-4 claddings. An X-ray diffraction (XRD) analysis was carried out for temperatures ranging from room temperature to $1250^{\circ}C$ for the oxide layer to verify the oxide crystal structure at each oxidation temperature.
Keywords
LOCA; Zirconium; Cladding; Zircaloy-4; HANA;
Citations & Related Records

Times Cited By Web Of Science : 1  (Related Records In Web of Science)
Times Cited By SCOPUS : 2
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